Recent content by Aly_19f

What are the most important fission products should I include/care about that comes out from the MCNP output?

I still don't know how to deal with the problem, in UO2 the sum of the Uranium atom fractions is equal one whatever the enrichment is. But by applying the same method in the MOX it is always >1. Is there any textbook or tutorial about burnup calculations?

Hey there, I'm working on an MCNPX modelling for SCWR using different clads and fuels, the first fuel was UO2(5%) and I have calculated the number density correctly since there was only one vector U. But now I don't know how top deal with the Th+U233 due to the existence of Thorium. Can anyone...

Hi, Is there any tutorial or pdfs that can help me with the MCNP output data? I'm working on the criticality of the SCWR, and I designed the fuel assembly and run it on the MCNP, but I have no idea about data extraction.

I'm very thankful for your answer, these links will help me a lot. Thank you.

Hi, I'm working on an MCNPX design for the Supercritical Light Water Reactor, and I want to know how does the density of the water -which plays the role of the coolant and moderator- change with temperature? I think the pressure is fixed at 25MPa, but the temperature of the water may vary, Does...

What does the number 0.62 refer to? Does it the water density at high temperature?

I'm very thankful to you, and I apologize for the fatal mistake of the title but I couldn't edit it when I saw your reply two days ago.

How do I express the temperature in the cell cards of the MCNP?, Say the temperature of the fuel is 500K, how do I write it as the following PWR example?